Radiation Safety Information Computational Center

Oak Ridge National Laboratory
Post Office Box 2008
Oak Ridge, Tennessee 37831-6362
Managed by
Lockheed Martin Energy Research Corp.
for the U.S. Department of Energy
under contract DE-AC05-96OR22464
Phone No. 423-574-6176
FAX 423-574-6182
Internet: PDC@ORNL.GOV
WWW: http://www-rsicc.ornl.gov/rsic.html
No. 394 October 1997
Let us read with method, and propose to ourselves an end to what our studies may point. The use of reading is to aid us in thinking.--Edward Gibbon

Mastercard or Visa

The Radiation Safety Information Computational Center is now accepting credit card payment for those code/data library acquisitions that require a fee. On receipt of a written request, RSICC will forward an invoice to cover the costs involved. The invoice can then be returned by mail or fax with the necessary credit card information.

CHANGES TO THE COMPUTER CODE COLLECTION

The NEA Data Bank contributed a personal computer version of this finite-element model of waste and water transport through saturated-unsaturated porous media. FEMWASTE is a two-dimensional transient model for the transport of dissolved constituents through porous media. The waste transport model is compatible with the water flow model (FEMWATER) for predicting convective Darcy velocities in porous media which may be partially saturated.

The PC package is based on the 1980 CDC versions of the codes, which were developed at ORNL. The Lahey F77L3/EM-32 Version 5.2 compiler was used to create the included executables, which can be run in a DOS window of Windows95. The package is transmitted on one 3.5-in. DS/HD (1.44MB) diskette in a self-extracting compressed DOS file. References: ORNL-5601 (1981), ORNL/TM-8328 (1982), ORNL-5567 (1980), and ORNL/TM-8327 (1982). Fortran 77; IBM PC (C00451/PC386/00).

The Institute for Physics and Nuclear Engineering, Bucharest-Magurele, Romania, through the NEA Data Bank, Issy-les-Moulineaux, France, contributed a newly frozen version of this code system designed to calculate energy-averaged cross sections of particle induced nuclear reactions. The new version, designated STAPRE-H95, was improved by the inclusion of realistic particle-hole state density formulae and full geometry-dependent hybrid (GDH) model description of the alpha-particle pre-equilibrium emission. Enlarged optical potential basis and the possibility to handle parameter sets of volume integrals of the real and imaginary potentials are now also available.

The Microsoft Fortran 77 Compiler v. 5.1 was used to create the executable load module included in the package. The code also runs on VAX/VMS computers. The package is transmitted on one 3.5-in. (1.44MB) DS/HD diskette in a self-extracting compressed DOS file which includes the source files, PC executable file, test case input data and output in DOS format. References: NP-83-1994 (Oct. 1994), NP-86-1995 (Sept. 1995), and J. Phys. G:20, 613-635 (1994). Fortran 77; IBM PC and VAX (P00325/MNYCP/01).

Idaho National Engineering Laboratory, Idaho Falls, Idaho, contributed this utility program to couple CCC-200/MCNP4A from LANL with CCC-371/ORIGEN2.1 from ORNL. MOCUP is a series of utility and data manipulation programs to solve time- and space-dependent coupled neutronics/isotopics problems. The neutronics calculation is performed by MCNP (version 4a or later), and the depletion and isotopics calculation is performed by ORIGEN2. MOCUP consists of three utility programs to search the MCNP output and tally files for relevant cell and tally parameters, prepare ORIGEN2 input files and execute the ORIGEN2 runs, and search ORIGEN2 punch files for relevant isotope concentrations and produce new MCNP input files. A graphical user interface based on X11 and the Motif tool kit provides for execution convenience.

MOCUP is written in C for DEC Alpha workstations with OSF/1 or HP workstations with HP-UX. Note that this package does not include MCNP (code and data), ORIGEN2.1, X11R4 and MOTIF, which must be installed on the computer before using MOCUP. MOCUP compilation requires an ANSI C compiler. The package is transmitted on one 3.5-in. (1.44MB) DS/HD diskette in a Unix compressed tar file. Reference: INEL-95/0523 (September 1995). HP and SGI; C (P00365/DALPU/00).

CONFERENCES, COURSES, SYMPOSIA

RSICC attempts to keep its users/contributors advised of conferences, courses, and symposia in the field of radiation protection, transport, and shielding through this section of the newsletter. Should you be involved in the planning/organization of such events, feel free to send your announcements and calls for papers via email to raf@ornl.gov.

Technologies for the New Century

The 1998 ANS Radiation Protection and Shielding Division Topical Conference, "Technologies for the New Century" will be held in Nashville, Tennessee, April 19­23, 1998. The General Chairman is Robert W. Roussin (rwr@ornl.gov) and the Technical Chairman is D. T. Ingersoll (dti@ornl.gov). Information about the conference can be found at http://www-rsicc.ornl.gov/RPS98/rps98.htm.

Reactor Analysis, Radiation Transport, and Criticality Safety Short Courses

The Department of Nuclear Engineering at the University of Tennessee-Knoxville is offering two five-day short courses of interest to radiation transport specialists during Tennessee Industries Week (TIW-33), May 18-22, 1998.

Computational Methods in Reactor Analysis and Shielding: Engineers, scientists, and technical managers who wish to increase their knowledge and understanding of the computational methods and computer codes currently used in nuclear reactor analysis and shielding will be interested in this intensive one-week short course. A good understanding of the neutronic models and associated numerical methods employed in the codes is essential for the successful use of the codes in designing new systems or improving the performance and safety of existing systems.

Areas to be covered include multidimensional diffusion theory methods and perturbation theory methods for applications in reactor statics, space dependent kinetics, and fuel depletion; transport theory methods including the discrete ordinates method, integral transport theory, and the Monte Carlo method; and cross section generation and processing utilizing the AMPX and SCALE systems developed at the Oak Ridge National Laboratory.

Special emphasis in the course is placed on the Monte Carlo method because of its widespread use and importance for nuclear system analysis brought about primarily by the increased availability of high performance workstations. The course ends at noon on Friday.

Monte Carlo Analysis: This course is designed specifically for the practicing engineer engaged in shield design and does not presume any prior knowledge of Monte Carlo methods. However, some understanding of radiation transport physics is desirable. A wide range of topics will be presented that will lead to a good understanding of the basics of Monte Carlo analysis and the specialized applications of Monte Carlo methods to practical shielding problems. Many advanced topics will be included that will promote the best use of existing computer code systems. Special attention will be paid to the understanding and Monte Carlo implementation of the adjoint analysis. Advantages and disadvantages of the adjoint mode versus the forward mode of analysis will be described including several practical applications of the adjoint mode of Monte Carlo analysis. Variance reduction techniques will be developed in a comprehensive fashion for both forward and adjoint calculations. The versatile computer code system, MORSE, will be described to illustrate the general features of Monte Carlo computer programs. The relationships of the Monte Carlo methods to other methods of solving radiation transport problems, such as discrete ordinates, will be described, as well as computational advantages and disadvantages of Monte Carlo versus the other methods. This course will cover, in depth, the theory and mathematics a user must have in order to understand and use the Monte Carlo method effectively to solve difficult problems in radiation transport.

Nuclear Criticality Safety: Engineers, scientists, and technical managers who wish to increase their knowledge and understanding of nuclear criticality safety will be interested in this intensive one-week short course. The topics covered in the course are based primarily on the experience of the six instructors which totals over 130 years of nuclear criticality safety related experience. Such a wealth of experience needs to be shared with the criticality safety community including both new professionals in the field as well as experienced professionals.

The course topics include illustrative applications using the SCALE system developed at the Oak Ridge National Laboratory with emphasis on the Monte Carlo code KENO Va, standards, regulations, review of accidents, hand calculation methods, subcritical limits, code validation techniques, emergency response, process upsets and recovery actions, and transient excursion modeling. The course ends at noon on Friday. The registration fee is $1195 per person for each course. The deadline for registration in these three courses is May 4, 1998. For additional information contact Lydia Salmon, Dept. of Nuclear Engineering, University of Tennessee, Knoxville, TN 37996 (phone 423-974-2525; email lsalmon@utk.edu). If you have access to the internet, you may also register via the website at http://www.engr.utk.edu/dept/nuclear/TIW.html.

Practical MCNP for the HP, Medical Physicist and Rad Engineer

MCNP made easy! The Los Alamos MCNP code is a general and powerful Monte Carlo transport code for photons, neutrons, and electrons. It is now supported on a variety of platforms and can run on everything from a laptop to a workstation.

This 4.5-day course is aimed at the health physicist, medical physicist or rad engineer with little or no experience with Monte Carlo techniques. The course will be offered on the following dates:

May 18-22, 1998 (registration deadline: 5/8/98)
August 10-14, 1998 (registration deadline: 7/31/98)

The focus is almost entirely on the application of MCNP to solve a variety of practical problems in radiation protection, radiation shielding, and dosimetry. The intent is to "jump start" the student toward using MCNP productively. Extensive practice sessions are conducted on a Windows-based personal computer platform.

Topics will include:

Students will be provided with a comprehensive class manual and a diskette containing all of the practice problems. This course has been granted 32 Continuing Education Credits by the AAHP. The course is offered by the Health Physics Measurements Group at the Los Alamos National Laboratory.

For further information, please contact Dick Olsher, 505-667-3364, e-mail: dick@lanl.gov. The course will be held at the University of New Mexico-Los Alamos Campus. Registration is $1500 per person.

Make checks payable to the University of California (checks must be in U.S. dollars on a U.S. bank) and mail together with your address, phone and fax numbers to:

Group ESH-4
MCNP Class/Paulette Sanchez
Mail Stop G761
Los Alamos National Laboratory
Los Alamos, NM 87545

Inquiries regarding registration and class space availability should be made to Paulette Sanchez (phone 505-665-6068, fax: 505-665-6071).

International Conference on the Physics of Nuclear Science and Technology

The "International Conference on the Physics of Nuclear Science and Technology" will be held October 5-8, 1998, at the Radisson Hotel, Islandia, Long Island, New York. The conference is sponsored by the Reactor Physics Division and the Long Island Section of the American Nuclear Society. Cooperating organizations include the Canadian Nuclear Society, the Korea Nuclear Society, the Croatia Nuclear Society, the Israel Nuclear Society, the National Resource Center for Plutonium, and, pending approval, the OECD/Nuclear Energy Agency and European Nuclear Society. Summaries are requested in the following technical areas:
  • Nuclear Data
  • Neutron/Reactor Physics
  • Reactor Analysis
  • Particle Transport
  • Monte Carlo Calculations
  • Numerical Methods
  • Non-Linear Dynamics
  • Transient Phenomena
  • Space-Time Kinetics
  • Coupled Neutronics
  • Thermal Hydraulics
  • Neutron Sources
  • Core Monitoring
  • Incore Fuel Management
  • Reactor Physics Standards
  • Reactor Physics Benchmarks
  • Nuclear Safeguards
  • Nuclear Instrumentation
  • Measurement Techniques
  • Fast Neutron Penetration
  • Neutron Dosimetry
  • Research & Test Reactors
  • Analysis of Nuclear Systems
  • Physics of MOX Fuels
  • Medical Applications
  • Space Applications
  • Spallation Physics
  • Actinide Burners
  • High Burnup Fuel

The deadline for summaries is January 5, 1998. Authors will be notified by March 15, 1998, and the deadline for camera-ready full papers is May 15, 1998. Summaries should be 1000-1500 words with tables and figures counting as 150 words each. Four copies of the summary should be sent to the Technical Program Chairman, Dr. Dimitrios Cokinos, Brookhaven National Laboratory, Building 197C, Upton, NY 11973-5000 USA (phone: 516-344-2146; fax: 516-344-7533; email: cokinos@bnl.gov).

Additional information may obtained at: http://www.dne.bnl.gov/html/confweb/conf-98.htm.

5th International Conference - Application of Semiconductor Detectors in Nuclear Physical Problems

The 5th International Conference "Application of Semiconductor Detectors in Nuclear Physical Problems" will be held May 18-22, 1998, in Riga, Latvia. The conference is being organized by Baltic Scientific Instruments and other organizations in cooperation with IAEA. Topics include:

For further information, please contact Baltic Scientific Instruments, Ganibu Dambis 26, P.O. Box 33, Riga, LV-1005, Latvia (phone: 371-2383947; fax: 371-7354677; email: bsi@bsi.mt.lv). Additional information may be obtained at the following world-wide web site: http://bsi.mt.lv/Intern_conf.htm.

Calendar

Your attention is directed to the following events of interest.

November 1997

Introduction to Medical Dosimetry, Nov. 3-7, 1997, a continuing education course offered by the University of Texas at San Antonio. Contact: The University of Texas Health Science Center at San Antonio, Continuing Medical Education, 7703 Floyd Curl Dr., San Antonio, TX 78284-7980 (phone 210-567-4491; fax 210-567-6964).

Nuclear Applications of Accelerator Technology, Nov. 16-20, 1997, Albuquerque, New Mexico, sponsored by the Accelerator Applications Technical Group of the American Nuclear Society. Contact: Dr. L. Warren Funk, AccAPP '97 Tech. Prog. Comm., Westinghouse Savannah River Co., Savannah River Site, 703-45A, Aiken, SC 29808, USA (phone 803-725-2797; fax 803-725-8727; email warren.funk@srs.gov).

December 1997

International Conference and Exhibition "Plant Life Management and Plant Life Extension in Nuclear Facilities," Dec. 8-10, 1997, Prague, Czech Republic, organized by Nuclear Engineering International. Contact: Alan Wagstaff, Events Manager, Nuclear Engineering International, Wilmington Publishing, Wilmington House, Church Hill, Wilmington, Dartford, Kent, DA2 7EF, UK (phone 44-1322-277788, fax 44-1322-273748).

January 1998

X-Ray Mammography, Basic Physics and Quality Assurance, Jan. 12-13, 1998, a continuing education course offered by the University of Texas at San Antonio. Contact: The University of Texas Health Science Center at San Antonio, Continuing Medical Education, 7703 Floyd Curl Dr., San Antonio, TX 78284-7980 (phone 210-567-4491; fax 210-567-6964).

Medical Radiation Safety Physics, Jan. 14, 1998, a continuing education course offered by the University of Texas at San Antonio. Contact: The University of Texas Health Science Center at San Antonio, Continuing Medical Education, 7703 Floyd Curl Dr., San Antonio, TX 78284-7980 (phone 210-567-4491; fax 210-567-6964).

Diagnostic Medical Physics, Jan. 15, 1998, a continuing education course offered by the University of Texas at San Antonio. Contact: The University of Texas Health Science Center at San Antonio, Continuing Medical Education, 7703 Floyd Curl Dr., San Antonio, TX 78284-7980 (phone 210-567-4491; fax 210-567-6964).

Radiation Oncology Physics, Jan. 16, 1998, a continuing education course offered by the University of Texas at San Antonio. Contact: The University of Texas Health Science Center at San Antonio, Continuing Medical Education, 7703 Floyd Curl Dr., San Antonio, TX 78284-7980 (phone 210-567-4491; fax 210-567-6964).

Nuclear Medicine Physics, Jan. 17, 1998, a continuing education course offered by the University of Texas at San Antonio. Contact: The University of Texas Health Science Center at San Antonio, Continuing Medical Education, 7703 Floyd Curl Dr., San Antonio, TX 78284-7980 (phone 210-567-4491; fax 210-567-6964).

Radiation Safety Officer's Course, Jan. 19-23, 1998, a continuing education course offered by the University of Texas at San Antonio. Contact: The University of Texas Health Science Center at San Antonio, Continuing Medical Education, 7703 Floyd Curl Dr., San Antonio, TX 78284-7980 (phone 210-567-4491; fax 210-567-6964).

February 1998

Health Physics Society Midyear Topical Meeting, Feb. 8-11, 1998, Mobile, Alabama. Contact: Health Physics Society, Suite 402, 1313 Dolley Madison Blvd., McLean, VA 22101-3926 (phone 703-790-1745; fax 703-790-2672; email: hpsburkmgt@aol.com).

Medical Dosimetry Review, Feb. 23-27, 1998, a continuing education course offered by the University of Texas at San Antonio. Contact: The University of Texas Health Science Center at San Antonio, Continuing Medical Education, 7703 Floyd Curl Dr., San Antonio, TX 78284-7980 (phone 210-567-4491; fax 210-567-6964).

April 1998

34th Annual Meeting of the National Council on Radiation Protection and Measurements, Apr. 1-2, 1998, Arlington, VA. Contact: National Council on Radiation Protection and Measurements, Suite 800, 7910 Woodmont Ave., Bethesda, MD 20814-3095 (phone 301-657-2652).

Technologies for the New Century, 1998 ANS Radiation Protection and Shielding Division Topical Conference, Apr. 19-23, 1998, Nashville, Tennessee. Contact: Dan T. Ingersoll, Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN 37831-6363 (fax 423-574-9619).

May 1998

Radiation Oncology Resident's Review in Radiation Oncology Physics and Radiation Biology, May 11-15, 1998, a continuing education course offered by the University of Texas at San Antonio. Contact: The University of Texas Health Science Center at San Antonio, Continuing Medical Education, 7703 Floyd Curl Dr., San Antonio, TX 78284-7980 (phone 210-567-4491; fax 210-567-6964).

Physicist's Review in Radiation Oncology Physics, May 11-15, 1998, a continuing education course offered by the University of Texas at San Antonio. Contact: The University of Texas Health Science Center at San Antonio, Continuing Medical Education, 7703 Floyd Curl Dr., San Antonio, TX 78284-7980 (phone 210-567-4491; fax 210-567-6964).

Computational Methods in Reactor Analysis and Shielding, May 18-22, 1998, Knoxville, Tennessee, a short course offered by the University of Tennessee-Knoxville. Contact: Lydia Salmon, Dept. of Nuclear Engineering, University of Tennessee, Knoxville, TN 37996 (phone 423-974-2525; email lsalmon@utk.edu).

Nuclear Criticality Safety, May 18-22, 1998, Knoxville, Tennessee, a short course offered by the University of Tennessee-Knoxville. Contact: Lydia Salmon, Dept. of Nuclear Engineering, University of Tennessee, Knoxville, TN 37996 (phone 423-974-2525; email lsalmon@utk.edu).

Monte Carlo Analysis, May 18-22, 1998, Knoxville, Tennessee, a short course offered by the University of Tennessee-Knoxville. Contact: Lydia Salmon, Dept. of Nuclear Engineering, University of Tennessee, Knoxville, TN 37996 (phone 423-974-2525; email lsalmon@utk.edu).

Radiation Safety Officer's Course, May 18-22, 1998, a continuing education course offered by the University of Texas at San Antonio. Contact: The University of Texas Health Science Center at San Antonio, Continuing Medical Education, 7703 Floyd Curl Dr., San Antonio, TX 78284-7980 (phone 210-567-4491; fax 210-567-6964).

June 1998

3rd International Meeting of Physicists in the Inca Region, June 15-20, 1998, Cusco, Peru. Contact: Jon Broadway, Internatl. Corps on Environment (ICE), Auburn University, 75 Technacenter Drive, Montgomery, AL 36117-6035 (phone: 334-242-2777; fax: 334-242-2755; email: broadway@strudel.aum.edu).

July 1998

Health Physics Society Annual Meeting, July 12-16, 1998, Minneapolis, Minnesota. Contact: Health Physics Society, Suite 402, 1313 Dolley Madison Blvd., McLean, VA 22101-3926 (phone 703-790-1745; fax 703-790-2672; email: hpsburkmgt@aol.com).

June 1999

Conference on Radionuclide Metrology and its Application, June 7-11, 1999, Prague. Contact: Pavel Dryák, Czech Metrological Institute, Radiova 1, CZ 102 00 Prague, Czech Republic (phone: +420 2 67008244, fax: +420 2 67008466, email: pdryak@cmi.cz).

SEPTEMBER ACCESSION OF LITERATURE

The following literature cited has been reviewed and placed in the RSICC Information Storage and Retrieval Information System (SARIS), now searchable on the RSICC web server (http://www-rsicc.ornl.gov/rsic.html). This early announcement is made as a service to the shielding community. Copies of the literature are not distributed by RSICC. They may generally be obtained from the author or from a documentation center such as the National Technical Information Service (NTIS), Department of Commerce, Springfield, Virginia 22161. For literature listed as available from INIS contact INIS Clearinghouse, International Atomic Energy Agency, P.O. Box 100, A-1400 Vienna.

Radiation Shielding Literature

Health Phys., 73, 423-432 . . . Radionuclides in the Body: Meeting the Challenge Lauriston S. Taylor Lecture. . . . Bair, W.J. . . . September 1997.

Health Phys., 73, 465-472 . . . 60Co Contamination in Recycled Steel Resulting in Elevated Civilian Radiation Doses: Causes and Challenges. . . . Wushou P. Chang; Chang-Chuan Chan; Jung-Der Wang . . . September 1997 . . . National Yang Ming University, Taipei, Taiwan; National Taiwan University, Taipei, Taiwan.

Health Phys., 73, 488-493 . . . Non-Linear Radionuclide Transfer from the Aquatic Environment to Fish. . . . Pyle, G.G.; Clulow, F.V. . . . September 1997 . . . University of Saskatchewan, Saskatoon, Canada; Laurentian University, Sudbury, Ontario, Canada.

Health Phys., 73, 494-497 . . . A New Device to Measure the Activity Size Distribution of Radon Progeny in a Low Level Environment. . . . Tokonami, S.; Takahashi, F.; Iimoto, T.; Kurosawa, R. . . . September 1997 . . . National Institute of Radiological Sciences, Chiba, Japan; Waseda University, Tokyo, Japan.

Health Phys., 73, 524-526 . . . Environmental Radiation Dose in Semipalatinsk Area Near Nuclear Test Site. . . . Takada, J.; Hoshi, M.; Rozenson, R.I.; Endo, S.; Yamamoto, M.; Nagatomo, T.; Imanaka, T.; Gu . . . September 1997.

Health Phys., 73, 532 . . . Sex-Specific Tissue Weighting Factors. . . . Dunster, H.J. . . . September 1997.

Nucl. Sci. Technol., 34, 856-859 . . . Comparison of Line Beam Response Function for Gamma-Ray Skyshine Analysis Based on Single Scattering Method with the Monte Carlo Calculations. . . . Harima, Y.; Hirayama, H.; Sakamoto, Y.; Kurosawa, N.; Nemoto, M. . . . August 1997 . . . CRC Research Institute, Inc.; High Energy Accelerator Research Organization; Japan Atomic Energy Research Institute; Visible Information Center, Inc.

INDC(NDS)-344 . . . The IAEA Co-Ordinated Research Programme on Activation Cross Sections for the Generation of Long-Lived Radionuclides of Importance in Fusion Reactor Technology. . . . Pashchenko, A.B., ed. . . . July 1997 . . . IAEA Nuclear Data Section, Vienna, Austria.

INDC(NDS)-361 . . . Establishment of an International Reference Data Library of Nuclear Activation Cross Sections. . . . Pashchenko, A.B., ed. . . . July 1997 . . . IAEA Nuclear Data Section, Vienna, Austria. . . . Summary Report of the Second Research.

INDC(CCP)-403 . . . Selected Articles Translated from Jadernye Konstanty (Nuclear Constants) Volumes 3-4, 1994. . . . June 1997 . . . Translated by the IAEA.

JINR, 3, 53-67 . . . Estimation of the Radiation Environment and the Shielding Aspect for the POINT2 Area of the LHC. . . . Shabratova, G.; Leistam, L. . . . 1997 . . . European Laboratory for Particle Physics, Geneva, Switzerland.

KEK Proceedings 97-1 . . . Proceedings of the Third Workshop on Pulsed RF Sources for Linear Colliders (RF96). . . . Fukuda, S., ed. . . . April 1997 . . . High Energy Accelerator Research Organization. . . . Shonan Village Center, Hayama Kanagawa, Japan, April 8-12, 1996.

KEK Proceedings 97-2 . . . Proceedings of the Sixth Workshop on Japan Linear Collider (JLC). . . . Sugimoto, Y., ed. . . . April 1997 . . . High Energy Accelerator Research Organization. . . .University of Tokyo, Japan, December 4-5, 1996.

KEK Report 97-5 . . . Calculation for the Design of a 2 GeV/c Kaon Beam at the Japanese Hadron Facility. . . . Doornbos, J. . . . June 1997 . . . High Energy Accelerator Research Organization.

NUREG/CR-6506; ORNL/TM-13327 . . . Embrittlement Data Base, Version 1. . . . Wang, J.A. . . . August 1997 . . . Oak Ridge National Laboratory, Oak Ridge, TN.

ORNL/TM-13170/V3 . . . Characteristics of Spent Fuel from Plutonium Disposition Reactors Vol. 3: A Westinghouse Pressurized-Water Reactor Design. . . . Murphy, B.D. . . . July 1997 . . . Oak Ridge National Laboratory, Oak Ridge, TN.

ORNL/TM-13450 . . . R-Matrix Analysis of the 240Pu Neutron Cross Sections in the Thermal to 5700 eV Energy Range. . . . Derrien, H.; Bouland, O.; Larson, N.M.; Leal, L.C. . . . August 1997 . . . Oak Ridge National Laboratory, Oak Ridge, TN.

ORNL/TM-13495 . . . Integral Data Analysis for Resonance Parameters Determination. . . . Larson, N.M.; Leal, L.C.; Derrien, H. . . . September 1997 . . . Oak Ridge National Laboratory, Oak Ridge, TN.

Posted October 31, 1997 (afr)